ML19295C974
| ML19295C974 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Oyster Creek, Cooper, Pilgrim, Brunswick, Vermont Yankee, Duane Arnold, Quad Cities, FitzPatrick |
| Issue date: | 06/17/1974 |
| From: | Levine A GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19295C972 | List: |
| References | |
| NUDOCS 8010240685 | |
| Download: ML19295C974 (3) | |
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AFFIDAVIT T AAIG J. ISIDE A
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I, Aaron J. Levine, being duly sworn, depose and state as follows:
1.
My na:re is Aaron J. Levine. I am the ranager of Project Licensing Unit-I for General Electric Ccr.pany's Nuclear Energy Products Division.
In this position, I have been involved in the AEC review of the General Electric cr. agency core cooling systen (ECCS) evaluation redels, ca develogrant of the schedules for canpleting calculation and in coordination with the operators of plants subject to new ECCS evaluation.
2.
C-2neral Electric has been requested by the operators of the following plants to provide mgency core cooling system (ECCS) calculations for filing on August 5, 1974, pursuant to 10 CFR s 50.46:
DOCICf NO Vermont Yankee.......
50-271 50-325 Bnmswick-2 nill i,.x..................-m.,
sv Dresden-2 & -3...........
. 50-237 & 50-249 Cand Cities-1 & -2.....
50-254 & 50-265 Monticello................
50-263 Oyster Creek...............
50-219 50-220 Nine Mile Point Pilgria.................
50-293
'IVA-1, -2 & -3..............
50-259, 50-250 & 50-296 Peach Bottcm-2 & -3 50-277 & 50-278 50-298
.Ccoper Duane Arnold...............
50-331 Fitzpatrick 50-333 natch-1.................
50-321 c,rder to parform such calculations, it has been necessary for General tric to develop a new evaluation model to confoat to the requirements Can,ission regulations and to secure Atcr'ic Energy Carission (AEC)
- P cencurrence in use of the new mcdel. Tne calculations utilize new
' /on of21s in conjunction with the spacific paramaters for each
~?O plants and are perfor.ed for a nu-bar of loss-of-coolant
, for each plant of diff arent sizes, locations r.d other pmper-
.iciat to provide assurance that the entire sp;ctrts of 801024 u /
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<t Affidavit of Aaron J. Iavine, Continued
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s d u.l-postulated loss-of-coolant accidents (IOCA) is covered.
4.
C-eneral Electric's new evaluation model consists of the folicwing parts:
a.
Short-Tem Themal-Hydraulic l'Mel; b.
Transient critical Pcwer Faiel; c.
Iong-Tena Themal-Hydraulic Model; d.
Core Heat-op Model.
5.
The AEC Staff review of the individual rdels ccmmnced in January 1974.
These models have been under intensive review by the Staff since that tima and have been discussed with the Advisory Ccr:aittee on Reactor S'.feguards. Upon concurrence frcm the Staff with the first tm parts of the redel in Anril, specific plant calculations were ccr.renced. The calculations for the last parts of the mcdel will ccimence prcrtly at tha timc at which t'- ; -m.y outputs fran the first prtc of the mcxlel are available.
6.
The current schedule for ccnpletion of calculations for these 20 plants is July 15, 1974. The results of the calculations will be prcngtly ccm-piled and distributed for use by the plant operators in their filings.
Because of the segaential procedure of the calculational oparation, the results of all 20-plant calculations will beccme available essenHally sinultaneously.
7.
Each plant uas fumished with preliminary estimates of the raxi. ca average planar linear heat generation rate expected for it as a result of the application of the Appandix K criteria. These rcrain the test estirates of the calculated results at this time.
It is General Electric's cpinion that for rest plants these estimates are accurate to about 103.
Hectuse of the volina of calculational verk and the soccential nature Page 2 of 3 pages
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.e Affidavit of.Aaron J. Ievine, Continued of the calculational cparation, no 'mtter estirates will be available prior to the completion of the calculations.
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Subscribed and s'.surn to before me this / 7My of June,1974.
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